Book/Report

FZJ-2016-06744

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Vorträge über beschichtete Brennstoffteilchen, Brennelemente und graphitischeWerkstoffe für fortgeschrittene Hochtemperaturreaktoren auf der Jahrestagung Kerntechnik 1980

Rottmann, J. (Editor)FZJ* ; Binkele, L.FZJ* ; Büscher, R.FZJ* ; Brinkmann, U.FZJ* ; Delle, W.FZJ* ; Engelstätter, R.FZJ* ; Falta, G. ; Förthmann, R.FZJ* ; Gyarmati, E.FZJ* ; Haag, G.FZJ* ; Kennedy, C. R. ; Kleist, G.FZJ* ; Krautwasser, P.FZJ* ; Mehner, A.-W. ; O'Connor, M. F. ; Petersen, K.FZJ* ; Price, R. J. ; Reitsamer, G. ; Rind, W. ; Schenk, W.FZJ* ; Schulze, H. A.FZJ* ; Schulze, R.-E.FZJ* ; Stolba, G. ; Storch, S.FZJ* ; Wimmers, M.

1980
Kernforschungsanlage Jülich GmbH Zentralbibliothek, Verlag Jülich

Please use a persistent id in citations: http://hdl.handle.net/2128/13003

Report No.: Juel-Conf-0038

Abstract: This report is a compilation of the papers presented by staff of the Institute for Reactor Materials, KFA-Jülich, at the 1980 annual conference "Reaktortechnik", held in Berlin, 25-27th March 1980. In some cases, there were co-authors from other organisations. Where possible the manuscripts of the presentations have been reproduced, as well as the display cards shown during the poster session on the conference. In the presentations, the questions of the characterization of fuel particles and the retention of fission products are dealt with, and special attention is given to fission product release at very high temperatures. One presentationdeals with the disposal of fuel elements from the AVR. Another report presents the results of radiation experiments on the standard matrix material A3-3 of the THTR fuel elements; the changes in dimensions, creep coefficient and thermal conductivity were measured as functions of the fluence and the radiation temperature.Interim results obtained from long-term radiation experiments on reflector graphites for high and very high flux reactors are presented, and models for the calculation of dimensional changes in components subjected to fluctuating temperatures from data obtained in isothermal tests are discussed. The investigations reported were partly carried out for the Project "High Temperature Reactor Fuel Cycle" involving as partners the Gesellschaft für Hochtemperaturreaktortechnik mbH, Hochtemperaturreaktor-Brennelement GmbH, Hochtemperaturreaktorbau GmbH, Kernforschungsanlage Jülich GmbH, NUKEM GmbH, and SIGRI Elektrographit GmbH/Ringsdorff-Werke GmbH. The Project is financially the BMFT and the State of North Rhine-Westphalia.

Note: Jahrestagung Kerntechnik, Reaktortagung 1980 Kerntechnische Gesellschaft e.V. Deutsches Atomforum e.V. Berlin, 25.- 27. März 1980

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Contributing Institute(s):

1. Publikationen vor 2000 (PRE-2000 ; Retrocat)

Research Program(s):

1. 899 - ohne Topic (POF3-899) (POF3-899)

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Database coverage:

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